ML20108E366

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Annual Radioactive Effluent Release Rept for Jan-Dec 1995
ML20108E366
Person / Time
Site: Callaway Ameren icon.png
Issue date: 12/31/1995
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20108E364 List:
References
NUDOCS 9605100207
Download: ML20108E366 (45)
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Text

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DOCKET NO. 50-483 Umon Etscnuc s

l CALLAWAY PLANT .

I ANNUAL RADIOACTIVE EFFLUENT l RELEASE REPORT I

I JANUARY DECEMBER 1995 I

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I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

/ CALLAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY LICENSE NPF - 30 JANUARY.- DECEMBER 1995

TABLE OF CONTENTS

1.0 INTRODUCTION

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS 4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTES SHIPMENTS 6.0 RELATED INFORMATION 6.1 Unplanned Releases 6.2 Changes to the Process Control Program 6.3 Changes to the Offsite Dose Calculation Manual 6.4 Major Changes to Radwaste Treatment Systems 6.5 Land Use Census Changes 6.6 Inoperability of Effluent Monitoring Instrumentation 6.7 Instances of Liquid Holdup Tanks or Waste Decay Tanks Exceeding Technical Specification Limits 7.0 METEOROLOGICAL DATA 8.0 ASSESSMENT OF DOSES 8.1 Dose at the Site Boundary and Nearest Residence from Gaseous Effluents 8.2 Dose to the MEMBER OF THE PUBLIC 8.2.1 Dose at the Nearest Residence from Gaseous Effluents 8.2.2 Dose to the MEMBER OF THE PUBLIC from Activities Within the SITE BOUNDARY 8.3 Total Dese Due to the Uranium Fuel Cycle 8.4 Dose Due to Liquid Effluents

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TABLE OF CONTENTS Table 1A Annual Summation of Gaseous Releases Table 1B Annual Airborne Continuous and Batch Releases Table 2A Annual Summation of Liquid Releases Table 2B Annual' Liquid Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments I i Table 4 Cumulative Joint Frequency Distributions i Table 5 l

[ Dose at the SITE BOUNDARY and Nearest Resident -

Table 6 Dose to the MEMBER OF THE PUBLIC from Activities within the i SITE BOUNDARY I l

Table'7 Total Dose Due to the Uranium Fuel Cycle Table 8 Dose Due to Liquid Effluents l

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1.0 INTRODUCTION

This Annual Radioactive Effluent Release Report is submitted in accordance with Section 6.9.1.7 of the Callaway Plant Technical Specifications.

The report presents a summary of radioactivity released in liquid and gaseous effluents, and solid waste shipped from the Callaway Plant during the period from January 1, 1995 to December 31, 1995.

The information is presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.

All liquid and gaseous effluents discharged during this reporting period were in compliance with federal regulations and the limits of Union Electric Administrative Procedure APA-ZZ-01003, Offsite Dose Calculation Manual (ODCM).

2.0 SUPPLEMENTAL INFORMATION 2.1 Reculatory Limits Specified as follows are the Radiological Effluent Control (REC) limits applicable to the release of radioactive material in liquid and gaseous effluents.

2.1.1 Fission and Activation Gases (Noble Gases)

The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

2.1.2 Radiciodine, Tritium, and Particulates The dose rate due to Iodine-131 and 133, tritium and all radionuclides in particulate form with half-lives greater than eight (8) days released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 1500 mrem /yr to any organ.

The dose to a member of the public from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
b. During any calendar year: Less than or equal to 15 mrem to any organ.

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I 2.1.3 Liquid Efflut.nts The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the g concentrations specified in Appendix B, Table II, Column 2 to g 10CFR20.001 to 20.601 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/ml total activity.

The dose or dose commitment to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and
b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

2.1.4 Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any member of 3 the public due to releases of radioactivity and to radiation from Uranium fuel cycle sources shall be limited to less than or equal to g

25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

2.2 Maximum Permissible Concentrations 2.2.1 The maximum permissible concentration values specified in Appendix B, Table II, Column 2 to 10CFR20.001 to 20.601 are used to calculate release rates and permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/ml is used as the limiting concentration for dissolved and entrained noble gases in liquid effluents.

2.2.2 For gaseous effluents, maximum permissible concentrations are not utilized in release rate calculations since the applicable limits 3 are based on dose rate at the site boundary. The " Percent of Tech Spec Limit" for Table 1A is therefore not applicable to the Callaway 5 Plant.

2.3 Averace Enerov This requirement is not applicable to the Cr.llaway Plant radiological effluent monitoring program s.nce the release rate 3 limits for fission and activation gases in gaseous effluent are not based on the average energy of the radionuclide mixture.

g 2.4 Measurements and Acoroximations of Total Radioactivity Radionuclide concentrations in liquid and gaseous effluents were obtained by effluent sampling and radiological analysis in ,

accordance with the requirements of Table 9.3-A and Table 9.6-A of '

APA-ZZ-01003, Offsite Dose Calculation Manual.

i Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents. Composite samples were analyzed for Sr-89, )

Sr-90, and Fe-55 by an independent laboratory. Tritium and gross alpha were measured for both liquid and gaseous effluents using I!

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liquid scintillation counting and gas flow proportional counting techniques, respectively.

The total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged.

2.5 Batch Releases Summary information relating to batch releases of gaseous and liquid effluents to the environment from the Callaway Plant during this year is presented below.

2.5.1 Licuid PERIOD PERIOD UNITS JAN - JUN JUL - DEC Number of batch releases: 118 120 Total time period for batch Minutes 47878 54631 releases:

Maximum time period for batch Minutes 762 965 release:

Average time period for batch Minutes 406 455 releases:

Minimum time period for batch Minutes 1 218 release:

Average Missouri River flow Cubic 151369 100141 during periods of release of feet per effluent into the river: 1 second 2.5.2 Gaseous PERIOD PERIOD UNITS JAN - JUN JUL - DEC Number of batch releases: 38 37 Total time period for batch Minutes 58357 19308 releases:

Maximum time period for batch Minutes 26235 3870 release:

Average time period for batch Minutes 1536 522 releases:

Minimum time period for batch Minutes 1 15 release:

2.6 Unolanned Releases 2.6.1 Licuid Number of releases: 2 Total Activity released: 9.62E + 01 Ci 1

Lctier, S. Ternes United States Department of the Interior - Geological Suncy - Water Resource Disision to B.

Ilolderness, Union Electric Company, dated January 17.1996.

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I 2.6.2 Gaseous Number of releases: 2 Total Activity released: 6.05 E-02 Ci 3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS 3.1 The quantity of radioactive material released in gaseous effluents during the year is summarized in Tables 1A and 1B. During this year all gaseous effluents were considered as ground level releases.

4.0

SUMMARY

OF LIOUID RADIOACTIVE EFFLUENTS 4.1 The quantity of radioactive material released in liquid effluents during the year is summarized in Tables 2A and 2B. During this year there was no continuous release of liquid effluent from the plant.

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5.0 S_OLID WASTES 5.1 The quantities of radioactive material released in shipments of solid waste for burial and irradiated fuel transported from the site during the year are summarized in Table 3. The total quantity and radioactivity reported ist Table 3 for aach waste type was for waste buried and include wastes buried by waste reprOcessors after volume reduction. The activity and fractional abundance of each nuclide was determined for each waste type based upon radiochemical analysis by an independent laboratory. The curie concentration of each l nuclide listed in Table 3 was determined as the product of the 3 fractional abundance and the total curies shipped. Those nuclides which comprise at least it of the total activity for a particular waste type are presented in Table 3.

6.0 RELATED INFORMATION 6.1 Unclanned Releases Unplanned releases are: 1) Inadvertent or accidental releases of radioactive material; 2) Releases of radioactive material via normal l g

pathways without a release permit, proper authorization, or proper sampling and analysis; and 3) Releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.

There wore four unplanned releases during the reporting period.

6.1.1 On February 6, 1995, The Count Room Technician noted a sampling requirement deviation in the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> noble gas grab sample from the l

g unit vent required by APA-ZZ-01003, Table 9.2.a, Action Statement

40. With the Unit Vent radiation monitor (GT-RE-21B) out of service, Action Statement 40 allows continued release of effluent by this pathway for 30 days provided that grab samples are taken at l

g least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Contrary to this requirement, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> sampling period was exceeded by 19 minutes. This deviation was determined to be l caused by human error and was discussed with the personnel involved. 3 During this period there were no abnormal operational events that would have significantly increased the activity being released from the plant.

A complete description of this event is documented in suggestion occurrence solutien (SOS) 95-0162.

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6.1.2 On April 3, 1995, radioactivity was detected in the Auxiliary 3 oiler system by the auxiliary steam cundensate recovery radioactivity monitor. Follow-up sampling of the Auxiliary Boiler confirmed the presence of 12 radionuclides at the following concentrations.

H3 7.50E-06 pCi/ml Ce-144 6.10E-07 pCi/ml Cs-137 2.17E-06 pCi/ml Cs-134 9.23E-07 pCi/ml I-131 2.56E-07 pCi/ml Zr-95 4.36E-07 pCi/ml Nb-95 4.59E-07 pCi/ml Co-57 4.65E-08 mci /ml Co-58 7.49E-06 pCi/ml Co-60 3.20E-06 pCi/ml Mn-54 9.57E-07 pCi/ml Cr-51 3.35E-06 pCi/ml The plant operations department was notified immediately to ensure that area drains and boiler blowdown were routed to the liquid radwaste system. Attempts were made to blowdown the boiler to remove the contamination. However, low levels of activity still remained.

A 10CFR50.59 evaluation was initiated immediately along with an investigation to determine the source of the activity which had concentrated in the auxiliary boiler. The source of the activity was caused by the failure of four radwaste components. The failure of these four components coupled with the design and operation of the secondary liquid waste evaporator and the auxiliary steam system, allowed radioactivity to backflow into the auxiliary steam system.

Dose calculations were performed based on the isotopic analyses of the Auxiliary Boiler contents and the estimated volume of steam released from continue operation. The calculations were performed according to the methodology in the Offsite Dose Calculation Manual, APA-ZZ-01003.

The 10CFR50.59 evaluation concluded that the resulting doses to a member of the public from the release of radioactive material to the environment would be a small fraction of the regulatory dose limits.

Therefore, continued operation of the Auxiliary Boiler would not pose any significant safety or environmental concerns.

l 11 The Auxiliary Boiler operated continuously from April 3 through I )

May 11 and intermittently during the remainder of 1995. The 1995 post release evaluation for the Auxiliary Boiler showed that the I following activity was released to the environment during 1995, )

l H-3 1.36E-02 Ci Cr-51 2.25E-04 Ci Mn-54 1.14E-04 Ci ll g

Co-58 4.27E-04 Ci Co-60 3.45E-04 Ci Xe-135 1.36E-07 Ci Kr-85 7.54E-06 Ci l

g Co-57 4.06E-07 Ci  ;

Nb-95 4.53E-05 Ci Zr-95 3.12E-05 Ci Nb-97 1.73E-06 Ci lI g<

Tc-99m 5.22E-07 Ci Sb-125 2.34E-05 Ci Ru-105 3.99E-05 Ci l Rh-106 1.46E-05 Ci 3 Ru-106 1.46E-05 Ci '

I-131 2.64E-05 Ci I-132 6.18E-07 Ci I-133 2.35E-06 Ci l g

Cs-134 6.52E-05 Ci Cs-137 1.54E-04 Ci Ce-144 1.80E-05 Ci Pr-144 1.80E-05 Ci The maximum organ dose to a member of the public from these releases was calculated to be 3.67E-03 mrem which is negligible when compared to the quarterly and annual effluent control limits. As a result, the releases of radioactive material from operation of the Auxiliary Boiler did not endanger the health or safety of the public or the environment.

The activity released from the Auxiliary Boiler during 1995 is reported in Table 1A and 1B and is also included in the annual dose calculations (see Section 8.0)

A description of this event along with the completed safety evaluation and corrective actions to prevent recurrence was documented in Suggestion Occurrence Solution SOS 95-0610.

6.1.3 On May 12, 1995, a release occurred from Discharge Monitor Tank (DKr) A which resulted in the release of 1000 gallons of liquid effluent without the required dilution flow.

Release permit RP09-1995-LOO 83 was generated for the release of DMT A with a required dilution flow of 5000 GPM. However, during initiation of the release the status of two release checklist items was incorrectly communicated to the technician initiating the release. Due to the miscommunication, the steps of the checklist which require that the main control room be contacted to verify adequate dilution flow were not performed. In addition, a malfunction of plant equipment allowed the discharge to be initiated without the required dilution flow. When the technician notified the main control room that the release had been initiated, the control room identified that there was no dilution flow. At this ti:.ie the technician immediately terminated the release and the i control room initiated 6000 GPM dilution flow. The root cause of I IIl gl 5l l

this event was the failure of a plant component along with human error in completing the release checklist.

The post event evaluation showed that 4.54E-02 Ci of H-3, 6.13E-08 Ci of Co-58, and 3.85E-07 Ci of Co-60 was released to the environment without dilution flow. This resulted in a tritium concentration 4 times the Technical Specification 6.8.4 (e) (2) limits for tritium concentration in liquid effluent released to unrestricted areas as specified in Appendix B to 10CFR20, Table II, Column 2. The maximum organ dose to a member of the public from this event was calculated to be 1.80E-06 mrem which is negligible when compared to the quarterly and annual liquid effluent control limits. As a result, the release of radioactive material from this event did not endanger the health or safety of the public or the environment.

A complete description of this event is documented in SOS 95-1217 6.1.4 On October 9, a report was made to the control room that there was a water leak between Logan Creek and Highway 94. An outside equipment operator was dispatched and discovered a leak in the discharge line from the plant. The leak in the discharge line was approximately two miles upstream of the discharge point to the Missouri River.

This site is about 200 yards north of highway 94 and on the south bank of Logan Creek. The water was discharging into Logan Creek and draining to the Missouri River.

A routine inspection of discharge lire performed on May 15, 1995, found no evidence of leakage. The area was heavily flooded by the Missouri River during the months of June and July 1995. The discharge pipe would have stayed full of water due to river elevations until August 25, when the river level dropped below 511 feet. At sometime after August 25, the discharge pipe became buoyant causing a misalignment of the pipeline resulting in the break. For conservatism, it was assumed the break occurred on August 1 and an environmental evaluation was performed for the period of August 1 through October 9.

The release permits for liquid effluent releases during the period from August 1, through October 9, 1995, were evaluated to determine the activity and the dose commitment to an individual assuming release to Logan Creek. Considering the size of the hole on the pipe, it was estimated that 2000 gals / min was discharged into Logan Creek.

During this period, 96.2 Curies of radioactive material were released in liquid effluents to Logan Creek. Tritium was the major nuclide released and accounted for greater than 99 percent of the total activity. Listed below is the activity released to Logan Creek.

NUCLIDE ACTIVITY (Ci)

H-3 9.62E+01 Mn-54 9.29E-06 Co-58 5.62E-05 Co-60 8.92E-05 Nb-95 7.28E-06 Ru-106 1.39E-05 Sb-125 4.76E-06 Cs-134 1.97E-06 Cs-137 2.91E-05 Pr-144 1.88E-05 Ce-144 1.88E-05 Hf-181 1.39E-06 7 .

I All releases during this period were conducted according to existing plant procedures for discharging radioactive liquid effluents. The waste flow rate and dilution flow rate were set by the release l g

permits to assure concentration of radioactive material released to unrestricted areas was within concentration limits specified in 10CFR20.1-20.601, Appendix B, Table II Doses were calculated using methodology described in the Offsite Dose Calculation Manual, APA-ZZ-01003 and NUREG 0133. For this evaluation, near field mixing for Logan Creek was considered to be negligible.

The releases to Logan Creek resulted in a total committed dose to the maximum exposed individual of 0.0141 mrem to the total body and a maximum organ dose of 0.0164 mrem.

g In addition the quarterly and annual liquid effluent control limits were not exceed due to this g

event. Therefore, this event did not endanger the health or safety of the public or the environment.

The activity released into Logan Creek is reported in Table 2A and 2B and the additional dose due to this event is included in Table 8.

A description of this event was documented in SOS 95-1940.

6.2 Changes to the Process Control Program There were no changes made to Administrative Procedure APA-ZZ-01011,

" Process Control Program Manual", during this year.

6.3 Changes to the Offsite Dose Calculation Manual Revision 5 of Administrative Procedure APA-ZZ-01003, Offsite Dose Calculation Manual (ODCM) was approved February 16, 1995.

The changes incorporated into revision 5 include the following:

1) Removal of airborne pathway dose conversion factors for airborne particulate nuclides with half-lives of less than 8 days and removal of liquid and airborne pathway dose conversion factors for Carbon-14, Phosphorus-32, Nickel-63, and Tellurium-125m.
2) The meat, milk, and vegetation pathway dispersion parameters were removed and the applicability of the dispersion parameters and locations for calculating dose were clarified.
3) Changed the reporting frequency for the effluent release report from semiannual to annual.
4) Relocated Radiological Effluent Controls 9.1 and 9.2 to FSAR Chapter 16 and the radiological environmental monitoring sample locations to plant procedure FDP-ZZ-03001, " Radiologic-1 Environmental Monitoring Program"
5) Revised footnotes to the gaseous effluent sampling and analysis table to require additional sampling of the unit vent in the event of a reactor power transient, only if the unit vent noble i gas monitor shows an activity increase by a factor of 3 or greater. {

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6) Added a section providing instructions for determining the dose s

to a member of the public from the on-site storage of low level radioactive waste.

A complete copy of Administrative Procedure APA ZZ-01003, Revision 5 is included as Attachment 1.

6.4 Maior Chances to Radwaste Treatment Systems There were no changes to the plant during the year which would be considered a major change to a Liquid, Gaseous, or Solid Radwaste Treatment System.

6.5 Land Use Census Chances No changes were identified in critical receptor locations for dose calculations during 1995 Land Use Census.

6.6 Inocerability of Effluent Monitorino Instrumentation All effluent monitoring instrumentation was OPERABLE within limits specified in FSAR Chapters 16.3.3.6 and 16.3.3.7B during the year.

6.7 Instances of Liouid Holduo Tanks or Waste Gas Decay Tanks Exceedino Technical Soecification Limits All liquid tanks and waste gas decay tanks were within limits specified in FSAR Chapters 16.11.1 and 16.11.3 during the reporting period.

7.0 METEOROLOGICAL DATA The on-site meteorological data for this reporting period is presented in Table 4. The data is presented as Cumulative Joint Frequency Distributions of wind speed and wind direction by atmospheric stability class for the 10 and 60 meter tower elevations. Valid data recovery for 1995 was greater than 90% for all required parameters.

8.0 ASSESSMENT OF DOSES Assessment of doses to the maximum exposed individuals from gaseous and liquid effluents released was performed in accordance with Administrative Procedure APA-ZZ-01003 as described in the following sections. For all effluent released from the Callaway Plant during this year, the annual dose to the maximum exposed individuals was less than it of the Radiological Effluent Control Limits presented in Section 2.1 of this report.

8.1 Dose at the Site Boundarv from Gaseous Effluents The dose at the Site Boundary was due to plume exposure from noble gases, ground plane exposure, and inhalation. It was conservatively assumed a hypothetical maximum exposed individual was present at the Site Boundary location with the most limiting atmospharic dispersion parameter, based on actual meteorological conditions for the year.

Dose group.

was conservatively calculated using a child as the critical age The dose from gaseous effluent at the Site Boundary for 1995 is presented in Table 5.

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8.2 Dose to the MEMBER OF THE PUBLIC I! '

The MEMBER OF THE PUBLIC was considered to be a real individual, not occupationally associated with the plant, who used portions of the plant site for recreational or other purposes not associated with the plant operation. This individual's utilization of areas both inside and outside the Site Boundary was characterized for this calculation.

To evaluate total dose from the Uranium Fuel Cycle to any MEMBER OF THE PUBLIC, the critical MEMBER OF THE PUBLIC within the Site Boundary, and the Nearest Resident were evaluated. '

8.2.1 Dose at the Nearest Resident from Gaseous Effluent The dose to the Nearest Resident was due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion.

Dose was calculated at the nearest actual residence with the most limiting atmospheric dispersion, based on meteorological conditions g for the year. It was conservatively assumed that each ingestion g pathway (meat, milk, and veg6tation) existed at this location. Dose was conservatively calculated assuming the child as the critical age group. Dose from activities within the Site Boundary was negligible '

and not included in this calculation. j The doses to the Nearest Resident for 1995 are presented in Table 5. l 8.2.2 Dose to the MEMBER OF THE PUBLIC from Activities within the Site Boundary Based on existing land use within the Site Boundary, the MEMBER OF THE PUBLIC with the highest dose was a farmer. Dose from farming activities within the Site Boundary was due to direct radiation exposure, plume exposure from noble gases, ground plane exposure, and inhalation. The current tenant estimates spending 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> E per year working within the Site Boundary area. Dose was calculated using the adult farmer as the critical age group.

g Dose to the MEMBER OF THE PUBLIC from activities within the Site Boundary is presented in Table 6.

8.3 Total Dose Due to the Uranium Fuel Cycle Since there are no other Uranium Fuel Cycle facilities within 8 kilometers of the Callaway Plant, the total dose to the most likely exposed MEMBER OF THE PUBLIC resulted from direct radiation exposure and radioactive effluents from Callaway Plant itself. Therefore, Dose from mining, fuel fabrication, and waste disposal were not included in this calculation.

Since dose via liquid releases was conservatively evaluated, 3 reasonable assurance exists that no real individual received a significant dose from radioactive liquid release pathways. 5 There' ore, only dose to individuals from airborne pathways and dose resulting from direct radiation were considered in this assessment.

The total dose to the MEMBER OF THE PUBLIC within the Site Boundary (Table 7) was the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his 3 residence. It was assumed that each food ingestion pathway exists at his residence. Dose was calculated using the adult farmer as the g

critical age group, t

The total dose from the Uranium Fuel Cycle is presented in Table 7.

8.4 Dose Due to Licuid Effluents Dose due to liquid effluents assumed centributi'ons from the maximum exposed individual's consumption of fish and potable water, as appropriate. An adult was considered to be the maximum exposed individual in this assessment.

Since there are no potabla water intakes within 50 river miles of the discharge point to the Missouri River, the potable water pathway was not included in the dose assessment. Therefore, dose contribution from fish consumption accounted for 95% of the total dose from liquid effluents discharged to the river. Dose from recreational activities' contributed the additional 5%. It is conservatively assumed the hype'hetical c maximum exposed individual obtained his entire annual fish intake from near the plant discharge.

Total dose due to liquid effluents from Callaway Plant during the year is presented in Table 8.

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i TABLElA L

SEMIANNUAL SUMMATION OF GASEOUS RELEASES l ALL AIRBORNE EFFLUENTS QUARTERS 1 AND 2,1995

)

FIRST SECOND EST TOTAL  !

TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) l A. FISSION AND ACTIVATION GASES i

! 1. TOTAL RELEASE CURIES 3.90E+01 2.66E+00 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 5.01E+00 3.39E-01 I
3. PERCENT OF TECH SPEC LIMIT  % N/A N/A B. RADIOIODINES l
1. TOTAL IODINE-13i CURIES 2.05E-06 3.89E-05 23
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.64E-07 4.95E-06
3. PERCENT OF TECH SPEC LIMIT  % N/A N/A l

C. PARTICUL/iTES l

1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 1.58E-07 1.52E-03 30
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.03E-08 1.93E-04
3. PERCENT OFTECH SPEC LIMIT  % N/A N/A
4. GROSS ALPHA RADIOACTIVITY CURIES 1.89E-07 2.25E-07 D. TRITlUM
1. TOTAL RELEASE CURIES 9.44E+00 2.74E+01 14
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.21E+00 3.48E+00
3. PERCENT OF TECil SPEC LIMIT  % N/A N/A f a) Safety Analysis Calculation 87-0634)0, January 6.1988 I

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TABLE l A (continued) I l SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS l

QUARTERS 3 AND 4,1995 l

THIRD M TYPE OF EFFLUENT UNITS QUARTER FOURTH QUARTER EST TOTAL ERROR % (a) gl A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CURIES 2.72E+00 4.93E+00 20
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.43E-01 6.21E-01
3. PERCENT OF TECH SPEC LIMIT  % N/A N/A B. RADIOIODINES
1. TOTAL IODINE-131 CURIES 9.33E-07 1.69E-06 23
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.17E-07 2.13E-07
3. PERCENT OF TECH SPEC LIMIT  % N/A N/A g 5

C. PARTICULATES

1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 8.27E-07 1.97E-07 30
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.04E-07 2.47E-08
3. PERCENT OF TECH SPEC LIMIT  % N/A N/A
4. GROSS ALPHA RADIOACTIVITY CURIES 1.88E-07 2.32E-07 D. TRITIUM I
1. TOTAL RELEASE CURIES 3.1 IE+0i 3.18E+0! 14
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.91 E+00 4.00E+00
3. PERCENT OF TECH SPEC LIMIT  % N/A N/A (a) Safety Analysis Calculation 87-063-(X), January 6,1988 I

,,. 2 . o i I

TABLEIB l SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 1 AND 2.1995 CONTINUOUS RELEASES l BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

1. IT$SION GASE3 AR-41 CURIES 0.00E+00 0.00E+00 6.92E-01 3.26E-02 XE-133 CURIES 7.46E+00 1.69E+00 2.34E+01 3.73E-03 XE-135 CURIES 4.12E-01 1.22E-01 4.44E+00 3.30E-05 XE-131M CURIES 0.00E+00 0.00E+00 3.64E-03 2.49E-03 KR-85 CURIES 0.00E+00 0.00E+00 1.60E+00 8.15E-01 KR-85M CURIES 0.00E+00 0.00E+00 1.75E-01 0.00E+00 XE-133M CURIES 0.00E+00 0.00E+00 6.36E-01 0.00E+00 KR-88 CURIES 0.00E+00 0.00E+00 1.73E-01 0.00E+00 KR-87 CURIES 0.00E+00 0.00E+00 1.53E-04 0.00E+00 XE-135M CURIES 0.00E+00 0.00E+00 9.94E-05 0.00E+00  ;

TOTAL FOR PERIOD CURIES 7.87E+00 1.81E+00 3.1 th0! 8.53E-01

2. IODINES I-131 CURIES 2.05E-06 1.24E-05 1.33E-09 2.65E-05 1132 CURIES 7.45E-05 3.56E-04 1.14E-06 1.70E-(M I-133 CURIES 7.38E-07 0.00E+00 1.08E-06 2.02E-04 1134 CURIES 0.00E+00 0.00E+00 8.81E-07 0.00E+00 1-135 CURIES 0.00E+00 0.00E+00 1.57E-06 0.00E+00 TOTAL FOR PERIOD CURIES 7.73E-05 3.68E-(M 4.67E-06 3.98E-04
3. PARTICULATES CO-57 CURIES 1.58E-07 0.00E+00 0.00E+00 4.05E-07 CE-144 CURIES 0.00E+00 0.00E+00 0.00E+00 1.79E-05 CO.58 CURIES 0.00E+00 2.74E-07 0.00E+00 4.27E-04 CO.60 CURIES 0.00E+00 1.98E-07 0.00E+00 3.44 E-04 CR-51 CURIES 0.00E+00 0.00E+00 0.00E+00 2.24E-04 CS-134 CURIES 0.00E+00 0.00E+00 0.00E+00 6.S t E-05 CS-137 CURIES 0.00E+00 0.00E+00 0.00E+(X) 1.53 E-04 MN-54 CURIES 0.00E+00 0.00E+00 0.00E+00 1.13E-04 NB-95 CURIES 0.00E+00 0.00E+00 0.00E+00 4.52E-05 PR-144 CURIES 0.00E+00 0.00E+00 0.00E+00 1.79E-05 RU-105 CURIES 0.00E+00 0.00E+00 0.00E+00 3.99E-05 R U- 106 CURiliS 0.00E+00 0.(X)E+00 0.00E+(X) 1.45E-05 SB-125 CURIES 0.00E+(X) 0.00E+00 0.00E+00 2.34 E-05 TC-99M CURIES 0.(X)E400 0.00E+00 0.00E+(X) 5.22E-07 Page 1 of 3

TABLE IB (continued)

SEMIANNUAL AIRBORNE CONTINUOUS AND B ATCH RELEASES GROUND LEVEL RELEASES =

FISSION GASES, IODINES, AND PARTICULATES QUARTERS 1 AND 2,1995 CONTINUOUS RELEASES B ATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

3. PARTICULATES ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 3.1IE-05 SR-89 CURIES 0.00E+00 1.33E-07 0.00E+00 0.00E+00 SR-90 CURIES 0.00E+00 4.22E-08 0.00E+00 0.00E+00 ALPHA CURIES 1.89E-07 2.25E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 3.47E-07 8.73E-07 0.00E+00 1.52E-03
4. TRITIUM H-3 CURIES 8.06E+00 2.70E+01 1.38E+00 3.88E-Ol I

I I

I I

I I

,,m, 3 I I

i TABLE IB (continued)

SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 3 AND 4,1995

- CONTINUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH

,?fdCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

1. FISSION GASES AR-41 CURIES 0.00E+00 0.00E+00 1.05E-01 4.33E-01 XE-133 CURIES 7.42E-01 3.47E+00 1.57E-02 4.83E-01 XE-135 CURIES 2.93E-02 0.00E+00 1.07E-04 2.35E-01 XE-131M CURIES 8.65E-01 0.00E+00 2.52E-04 0.00E+00 KR-85 CURIES 0.00E+00 0.00E+00 9.65E-01 0.00E+00 KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 2.35E-02 XE-133M CURIES 0.00E+00 1.57E-01 0.00E+00 KR-88 0.00E+00 CURIES 0.00E+00 0.00E+00 1.12E-04 4.18E-02 KR-87 CURIES 0.00E+00 0.00E+00 0.00E+00 2.88E-02 XE-135M CURIES 0.00E+00 0.00E+00 0.00E+00 1.31E-02 XE-138 CURIES 0.00E+00 0.00E+00 0.00E+00 4.79E-02 TOTAL FOR PERIOD CURIES 1.64E+00 3.63E+00 1.09E+00 1.31E+00
2. IODINES 1 131 CURIES 9.33E-07 1.69E-06 0.00E+00 0.00E+00 1-133 CURIES 3.77E-06 4.78E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 4.70E-06 6.48E-06 0.00E+00 0.00E+00
3. PARTICULATES CO-58 CURIES 0.00E+00 1.97E-07 0.00E+00 0.00E+(K)

SR-89 CURIES 6.28E-07 0.00E+00 0.00E+00 0.00E+00 SR-90 CURIES 1.99E-07 0.00E+00 0.00E+00 0.00E+00 ALPHA CURIES 1.88E-07 2.32E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 1.02E4)6 4.28E-07 0.00E+00 0.00E+00

4. TRITIUM H3 CURIES 3.NE+01 2.40E+01 7.29E-01 7.81 E+00 Page 3 of 3 l

TABLE 2A I! '

SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS I QUARTERS 1 AND 2,1995 FIRST SECOND EST TOTAL l TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) 3

  • P. AWN AND ACTIVATION PRODUCTS

.... a .

g

1. TOI AL RELEASE [NOT INCLUDING TRITIUM, GASES, ALPHA] CURIES 7.92E-04 5.34E-03 20
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.68E-09 1.24E-08
3. PERCENT OF APPLICABLE LIMIT  % N/A N/A B. TRITIUM
1. TOTAL RELEASE CURIES 3.-l i E+02 8.68E+01 14 i
2. AVERAGE DILUTED CONCENTRATION E DURING PERIOD uCi/ML 6.61 E-04 2.02E-04 g
3. edRCENT OF APPLICABLE LIMIT  % N/A N/A C. DISSOLVED AND ENTRAINED GASES B
1. TOTAL RELEASE CURIES 3.77E-02 1.15E-03 27 '
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.0lE-08 2.68E-09 D. GROSS ALPilA RADIOACTIVITY I  :
1. TOTAL REI EASE CURIES 1.97E-03 1.99E-04 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) GAL 4.94E+06 5.68E+06 10 F. VOLUME OF DILUTION WATER USED GAL 1.19E 8 1.08E+08 I

10 (a) Safety Analysis Calculation 87-063-00. January 6.198M I

1 I' l Page I of 2 Il l l

I'

, TABLE 2A (continued)

SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 3 AND 4,1995 THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE [NOT INCLUDING TRITIUM, GASES, ALPHA] CURIES 8.64E-N 1.04E-03 20
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.7)E-09 2.54E-09
3. PERCENT OF APPLICABLE LIMIT  % - N/A N/A B. TRITIUM
1. TOTAL RELEASE CURIES 1.50E+02 2.44E+02 14
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.70E-N 5.97E-N
3. PERCENT OF APPLICABLE LIMIT  % N/A N/A C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE CURIES 1.06E-03 2.42E-03 27
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.34E-09 5.90E-09 D. GROSS ALPil i RADIOACTIVITY
1. TOTAL RELEASE CURIES 1.43E-03 9.71E-03 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) GAL 5.79E+06 5.41E+06 10 F. VOLUME OF DILUTION WATER USED GAL 7.84 E+07 1.03E+08 10 (a) Safety Analysis Calculation 87-063-00, January 6.1988 Page 2 of 2 '

TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE IGLEASED QUARTERS 1 AND 2,1995 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

1. ALL NUCLIDES I

ALPHA CURIES 0.00E+00 0.00E+00 1.97E-03 1.99E-04 H-3 CURIES 0.00E+00 0.00E+00 3.l lE+02 8.68E+01 =

SR-90 CURIES d.00E+00 0.00E+00 2.49E-N 0.00E+00 XE-133 CURIES 0.00E+00 0.00E+00 3.56E-02 1.23E-N XE-135 CURIES 0.00E+00 0.00E+00 1.11E-03 7.94E-06 CO-60 CURIES 0.00E+00 0.00E+00 3.07E-04 2.72E-03 XE-133M CURIES 0.00E+00 0.00E+00 6.88E-04 0.00E+00 CS-137 CURIES 0.00E+00 0.00E+00 4.66E-05 1.35E 04 I-131 CURIES 0.00E+00 0.00E+00 2.20E-06 9.95E-06 XE-131M CURIES 0.00E+00 0.00E+00 2.57E-04 0.00E+00 CS-134 CURIES 0.00E+00 0.00E+00 1.27E-05 8.30E-06 CE-144 CURIES 0.00E+00 0.00E+00 7.17E-05 9.41 E-05 M N-54 CURIES 0.00E+00 0.00E+00 7.98E-06 1.20E-04 PR-144 CURIES 0.00E+00 0.00E+00 7.17E-05 9.41 E-05 TE-129 CURIES 0.00E+00 0.00E+00 2.37E-05 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 0.00E+00 8.37E-06 CO-58 CURIES O n0E+00 0.00E+00 0.00E+00 1.01 E-03 NB-95 CURIES 0.00E+00 0.00E+00 0.00E+00 1.87E-N CR-51 CURIES 0.00E+00 0.00E+00 0.00E+00 6.20E-N FE-59 CURIES 0.00E+00 0.00E+00 0.00E+00 2.03E-05 ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 1.20E-04 AG-110M CURIES 0.00E+00 0.00E+00 0.00E+00 1.llE-05 CE-141 CURIES 0.00E+00 0.00E+00 0.00E+00 4.44E-05 LA-140 CURIES 0.00E+00 0.00E+00 0.00E+00 1.30E-05 RU-106 CURIES 0.00E+00 0.00E+00 0.00E+00 9.32E-05 SN-l 13 CURIES 0.00E+00 0.00E+00 0.00E+00 1.43E-05 RU-103 CURIES 0.00E+00 0.00E+(X) 0.00E+00 1.66E-08 SB-125 CURIES 0.00E+00 0.00E+00 0.00E+00 3.21E-08 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 4.06E-06 ZR-97 CURIES 0.00E+00 0.00E+00 0.00E+00 2.81E-06 RU-105 CURIES 0.00E+00 0.00E+00 0.00E+00 1.31 E-05 KR 85 CURIES 0.00E+00 0.00E+00 0.00E+00 1.02E-03 TC-99M CURIES 0.00E+00 0.00E+00 0.00E+00 2.81 E-06 TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 3.1 I E+02 8.68E+01 I

I I

,_c I E

TABLE 2B (continued)

SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 3 AND 4,1995 ~

CONTINUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER I. ALL N'UCLIDES .

ALPHA CURIES 0.00E+00 0.00E+00 1.43E-03 9.71E-03 H-3 CURIES 0.00E+00 0.00E+00 1.50E+02 2.44E+02 XE 133 CURIES 0.00E+00 0.00E+00 8.74E-N 2.25E-03 XE-135 CURIES 0.00E+00 0.00E+00 2.08E-05 1.62E-04 CO-60 CURIES 0.00E+00 0.00E+00 2.52E-04 2.30E-04 CS-137 -

CURIES 0.00E+00 0.00E+00 1.45E-04 1.21E-05 XE-131M CURIES 0.00E+00 0.00E+00 1.69E-04 CS-134 0.00E+00 CURIES 0.00E+00 0.00E+00 9.02E-06 8.84E-06 CE 144 CURIES 0.00E+00 0.00E+00 3.04E-05 0.00E+00 MN-54 CURIES 0.00E+00 0.00E+00 3.28E-05 1.65E-05 PR-144 CURIES 0.00E+00 0.00E+00 3.04E-05 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 1.56E-04 7.64E-04 NB-95 l CURIES 0.00E+00 0.00E+00

' 2.39E-05 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 6.16E-06 0.00E+00 RU-106 CURIES 0.00E+00 0.00E+00 2.24E-05 0.00E+00 SN-113 CURIES 0.00E+00 0.00E+00 0.00E+00 2.50E-06 RU-103 CURIES 0.00E+00 0.00E+00 0.00E+00 2.76E-06 SB-125 CURIES 0.00E+00 0.00E+00 7.39E-06 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 0.00E+00 TC-101 2.17E-06 CURIES 0.00E+00 0.00E+00 1.46E-04 0.00E+00 HF-181 CURIES 0.00E+00 0.00E+00 2.23E-06 0.00E+00 CO-57 CURIES 0.00E+00 0.00E+00 0.00E+00 3.33E-06 TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 1.50E+02 2.44E+02 Page 2 of 2

I TAIRE3 I' SOLID WASTE & IRRADIATED FUEL SilIPMENTS 1995  ;

A. SOLID WASTE BURIED (DOES NOT INCLUDE IRRADIATED FUEL)

1. TYPE OF WASTE PERIOD PERIOD EST. TOTAL UNITS JAN - JUN JUL - DEC ERROR (%)
a. Spent resins, filter sludges m2 0.0 11.3 g evaporator bottoms, etc. Ci 0.00E+00 1.77E+02 i25%
b. Dry compressible waste, m5 0.0 7.1 g contaminated equipment, etc. Ci 0.00E+00 9.31E-02 i25% 5
c. Irradiated components, m' O.0 s 0.0 control rods, etc. Ci 0.00E+00 0.00E+00 i25%
d. Other m2 0.0 0.0 Ci 0.00E+00 0.00E+00 i25%
2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by Type of Waste)

PERIOD PERIOD JAN - JUN JUL - DEC Pe'rcent Percent Nuclide Abundance Curies Abundance Curies

a. Co-60 33.73% 5.97E+01 Ni-63 32.43% 5.74E+01 Cs-137 13.56% 2.40E+01 g

Fe-55 8.11% 1.44E+01 g Cs-134 8.01% 1.42E+01 Sb-125 1.23% 2.18E+00

b. Fe-55 46.94% 4.37E-02 Co-60 14.67% 1.37E-02

!!i- 6 3 11.05v 1.03E-02 Co-58 10.19% 9.49E-03 Mn-54 5.11% 4.76E-03 _

Cr-51 4.42% 4.12E-03

!!b - 9 5 2.27% 2.11E-03 Cs-137 1.76% 1.64E-03 Ob-125 1.59* 1.48E-03 Zr-M 1.04% 9.68E-04

c. l l l l
d. l l l l I

I Page 1 of 2 B.

TAllLE 3 (continued)  !

SOLID WASTE & IRRADIATED FUEL SIIIPMENTS I 1995

( 3. SOLID WASTE DISPOSITION:

Number of Mode of Class of Type of Shipments Transportati Destination Solid Waste Container on Shipped 10* Truck Scientific A LSA Ecology Group 1* Truck American Ecology A LSA Above shipments sent to waste reprocessors for volume reduction before burial.

2 l Cask l Barnwell, SC l C l LSA

4. SOLIDIFICATION AGENT:

None used.

D. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Mode of Shipments Transportation Destination 9

[

[

Page 2 of 2

TABLE 4 Union Electric - Callaway Plant Report DatcHime: 26-APR-199610:47:19.83 Meteorological Data Averages Using Hourly Averaged Data 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 I

% GOOD UNITS VALUES DATA Stability Class A-G E 98 %

Total Precipitation CM. 1.80E+02 90 %

10 Meter Level: Wind Speed Wind Direction Meter /Sec Degrees 3.31E+00 2.23E+02 100 %

96 %

3 W

Wind Direction Variability Degrees 1.27E+01 96 %

Reference Temperature Degrees C 1.23E+01 98 %

Dewpoint Degrees C 4.85E+00 99 %

60 Meter Level: Wind Speed Meter /Sec 5.17E+00 97 % 3 Wind Direction Degrees 2.15E+02 96 % 3 Wind Direction Variability Degrees 8.53E+00 98%

Dewpoint Degrees C NONE 0%

Temperature Difference 60 - 10 Degrees C 2.83E-01 98 %

I I

I I

I I-I I

Page I of 15 II I

TABLE 4 (continued)

Union Electric - Callaway Plant Report Date/ Time: 26-APR-199610:47:42.00 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: A l Wind Speed at 10.00 Meter Level (MPH) l-3 4-7' 8-12 13-18 19-24 >24 TOTAL N 0 3 2 0 0 0 5 l NNE O 1 1 0 0 0 2 NE 0 0 0 0 0 0 0 l ENE- 1 0 0 0 0 0 1 I

i E 1 1 0 0 0 0 2 ESE 0 4 4 0 0 0 8 SE I 19 7 1 0 0 28 SSE 0 21 10 4 0 0 35 S 0 29 18 2 2 0 51 SSW l 40 25 4 0 0 70 l

! SW l 22 15 1 0 0 39 WSW l 3 3 0 0 0 7 W 0 1 13 3 0 0 17 j WNW l 2 6 4 0 0 13 NW 0 2 4 0 0 0 6 NNW l 1- 0 0 0 0 2 TOT 8 149 108 19 2 0 286 Hours of Calm Data: 0 Hours of Invalid Data' "

i

}

l Page 2 of 15

l TABLE 4 (continued)

Union Electric - Callaway Plant Report Date/fime: 26-APR-199610:47:42.00 Meteorological Data g Totals of Hours at Each Wind Speed & Direction g 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: B I

Wind Speed at 10.00 Meter Level (MPH) l-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 7 0 0 0 8 NNE O 2 1 0 0 0 3 NE O 2 0 2 0 0 4 ENE O O O O O O 0 E O 3 2 0 0 0 5 ESE 0 5 8 1 0 0 14 SE O 8 18 2 0 0 28 SSE O 15 12 3 2 0 32 S 1 15 16 10 0 0 42 SSW 2 9 10 1 0 0 22 SW l 15 11 2 0 0 29 WSW 0 6 3 0 0 0 9 W 2 7 7 3 0 0 19 WNW 2 8 22 5 0 0 37 NW 0 5 9 0 0 0 14 E g

NNW l 0 3 0 0 0 4 TOT 9 101 129 29 2 0 270 liours of Calm Data: 0 Hours ofInvalid Data- 'O E

I Page 3 of 15

l )

I l TABLE 4 (continued) i Union Electric - Callaway Plant Report Date/ Time: 26-APR-199610:47:42.00 l

Meteorological Data  !

Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: C Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL i N 1 9 16 0 0 0 26 NNE 1 14 4 2 0 0 21 l NE 2 5 1 1 0 0 9 ENE 1 5 2 0 0 0 8 E 0 8 3 0 0 0 11 ESE 1 5 8 5 0 0 19 SE 2 12 12 2 0 1 29  !

SSE l 4 8 12 1 0 0 25 l S 3 14 19 6 1 0 43 SSW 2 13 9 4 0 0 28 SW l 15 5 1 0 0 22 WSW 0 10 6 3 0 0 19 W 0 7 7 7 1 0 22 .

WNW 2 13 3 3 0 1 22 NW l 11 11 3 0 0 26 NNW l 7 18 0 0 0 26 TOT 22 156 136 38 4 0 356 l Hours of Calm Data: 0 l Ilours of Invalid Data- '8 i

i l

Page 4 of 15

TABLE 4 (continued)

Union Electric - Callaway Plant Report Date/ rime: 26-APR-199610:47:42.00 Meteorological Data 3 Totals of Hours at Each Wind Speed & Direction g 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: D I

Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 56 63 7 1 0 136 NNE 5 45 32 1 0 0 83 NE 14 29 20 2 0 0 65 ENE 5 26 23 6 0 0 60 E 5 26 34 9 0 0 74 ESE 2 30 41 8 0 0 81 SE 16 59 84 13 1 0 173 SSE 11 57 67 11 1 0 147 S 11 49 49 22 1 0 132 SSW 7 39 40 13 1 1 101 SW 14 38 31 22 2 2 109 WSW 6 29 27 14 5 3 84 W 13 48 42 30 5 0 138 WNW l1 46 68 37 5 0 167 NW lI 71 73 36 2 0 193 NNW 10 81 85 11 6 0 193 TOT 150 729 779 242 30 6 1936 Hours of Calm Data: 1 3

liours of Invalid Data: 68 E 1

Page 5 of 15 L

TABLE 4 (continued)

Union Electric - Callaway Plant -

Report Date/ Time: 26-APR-199610:47:42.00 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 '

Stability Class: E l

Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL  !

N 28 102 112 18 0 0 260 NNE 21 99 39 1 0 0 160 l

NE 39 50 15 0 0 0 104 ENE 28 66 26 1 0 0 121 E 27 111 47 4 0 0 189 ESE 30 102 74 8 0 0 214 SE 20 149 164 11 0 0 344 SSE 23 126 142 0 0

]' 317 S 31 79 99 27 3 0 239 SSV/ 19 62 41 10 0 0 132 S\V 19 52 49 8 3 0 131 WSW 27 56 44 10 7 0 144 V/ 32 94 88 12 0 0 226 l WNW 31 104 91 14 0 0 240 NW 46 131 93 53 0 1 324 NNW 27 140 119 22 2 0 310 TOT 448 1523 1243 225 16 0 3455 Hours of Calm Data: 13 Hours of Invalid Data: 65 Page 6 of 15

TABLE 4 (continued)

Union Electric - Callaway Plant -

Report Date/ Time: 26-APR-199610:47:42.00 Meteorological Data Totals of Hours at Each Wind Speed & Direction 3

g1 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: F I

Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 22 34 0 5 3 0 64 NNE 29 39 4 3 4 0 79 I NE 38 24 4 0 0 0 66 ENE 48 35 2 0 0 0 85 E

ESE 26 30 25 43 2 2 0 0

0 0

0 0

53 75 l

l SE 38 141 26 0 0 0 205 SSE 35 153 38 0 0 0 226 ,

S 27 86 35 0 0 0 148

]

SSW 31 47 11 0 0 0 89 SW 15 41 9 0 0 0 65 WSW 16 15 6 0 0 0 37 I W 26 28 17 0 0 0 71 WNW 34 33 12 0 0 0 79 I NW 20 59 5 8 4 0 96 NNW 15 37 5 4 2 0 63 I TOT 450 840 178 20 13 0 1501 Hours of Calm Data: 15 Hours of invalid Data: 60 g

g Il l Page 7 of 15

TABLE 4 (continued)

Union Electric - Callaway Plant Report Date/ Time: 26-APR-199610:47:42.00 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: G Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 17 15 1 1 1 0 35 NNE 17 21 8 2 0 0 48 NE 33 5 2 0 0 0 40 ENE 23 7 0 0 0 0 30 E 9 2 0 0 0 0 11 ESE 14 1 0 0 0 0 15 SE 15 31 5 0 0 0 51 SSE 22 61 18 0 0 0 101 S 12 20 8 0 0 0 40 SSW 13 13 1 0 0 0 27 SW 16 21 2 0 0 0 39 WSW 8 1 3 0 0 0 12 W 14 5 7 2 0 0 28 WNW 13 8 0 0 0 0 21 NW 11 21 0 6 2 0 40 NNW 13 16 2 3 7 0 41 TOT 250 248 57 14 10 0 579 liours of Calm Data: 21 flours of invalid Data: 36 liours of Good Data: 8433 = 96.3% of Total flours Page 8 of 15

l TABLE 4 (continued)

Union Electric - Callaway Plant Report Daterrime: 26-APR-199610:47:58.47 i Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: A I

Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 1 4 0 0 0 6 NNE O 1 1 0 0 0 2 NE O 0 0 0 0 0 0 ENE O O O O O 0 0 E O 1 0 0 0 0 1 ESE O 3 1 2 0 0 6 SE O 8 16 4 0 0 28 SSE 0 11 18 3 0 0 32 S 0 18 23 14 1 2 58 SSW 0 19 48 8 0 0 75 SW 0 5 36 6 1 0 48 WSW 0 3 3 1 0 0 7 W 0 1 9 5 3 0 18 WNW 0 0 5 5 3 0 13 NW 0 0 4 3 0 0 7 NNW 0 0 0 0 0 0 0 TOT 1 71 168 51 8 2 301 Hours of Calm Data: 0 Hours of Invalid Data: 7 I

Page 9 of 15 I

TABLE 4 (continued)

Union Electric - Callaway Plant Report Date/ rime: 26-APR-199610:47:58.47 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: B Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 7 0 0 0 7 NNE O 1 2 0 0 0 3 NE O 1 0 2 0 0 3 ENE O 2 0 0 0 0 2 E O 1 0 0 1 0 2 ESE O 3 13 2 0 1 19 SE O 6 14 5 0 0 25 SSE O 10 14 8 4 0 36 S 1 9 14 10 7 1 42 SSW l 8 17 5 1 0 32 SW 0 7 16 6 1 0 30 WSW 0 9 4 2 0 0 15 W 0 6 8 4 3 0 21 WNW 0 5 10 14 2 1 32 NW l 1 9 4 0 0 15 NNW 0 0 4 0 0 0 4 TOT 3 69 133 62 19 2 288 Hours of Calm Data: 0 Hours of Invalid Data- '

Page 10 of 15

1 TABLE 4 (continued) l Union Electric - Callaway Plant Report Date/ Time: 26-APR-199610:47:58.47 Meteorological Data  ;

Totals of Hous at Each Wind Speed & Direction 1-jAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 '

Stability Class: C I

Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 2 17 0 0 0 19 NNE 1 10 13 2 0 0 26 NE O 5 2 1 0 0 8 ENE 2 5 2 1 0 0 10 I E O 7 2 1 0 0 10 ESE O 3 13 5 1 0 22 SE O 12 13 3 2 0 30 SSE 2 11 12 3 0 0 28 S 0 16 19 10 3 1 49 SSW 2 8 10 3 4 0 27 SW 0 13 13 3 2 0 31 WSW 0 5 4 3 2 1 15 W 0 3 10 5 4 2 24 WNW l 9 4 4 2 1 21 NW 0 11 9 8 1 0 29 NNW 3 4 14 5 2 0 28 TOT 11 124 157 57 23 5 377 I

Hours of Calm Data: 0 Hours of Invalid Data: 7 g,

g Page ! I of 15 I

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TABLE 4 (continued)

Union Electric - Callaway Plant Report Dateffime: 26-APR-199610:47:58.47 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: D Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 24 72 23 2 6 129 NNE 2 32 47 11 0 0 92 NE 6 34 21 12 2 0 75 ENE 5 14 23 12 3 0 57 E 4 12 32 19 0 0 67 ESE 2 25 44 14 3 0 88 SE 8 30 59 47 2 1 147 SSE 4 38 67 36 6 1 152 S 3 36 56 38 11 3 147 SSW I 26 41 25 8 2 103 SW 3 30 38 26 15 10 122 WSW 3 19 21 21 11 12 87 W 9 22 32 34 19 11 127 WNW 4 21 51 46 27 8 157 NW 4 36 79 49 22 7 197 NNW 3 44 74 29 6 0 156 TOT 63 443 757 442 137 61 1903 Hours of Calm Data: 1 Hours of Invalid Data: 101 Page 12 of 15

TABLE 4 (continued)

Union Electric - Callaway Plant Report Date/ Time: 26-APR-199610:47:58.47 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: E Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 42 125 78 10 0 261 NNE 8 44 100 31 0 0 183 NE 8 41 64 5 0 0 118 ENE 5 30 68 14 1 0 118 I E 9 43 85 23 3 0 163 ESE 6 49 120 45 3 0 223 SE 4 26 129 128 5 1 293 SSE 7 25 125 138 29 0 324 S 3 27 105 111 22 3 271 SSW 8 35 64 58 13 0 178 SW 4 31 44 50 17 4 150 WSW 8 22 46 42 9 8 135 W 6 22 61 90 17 2 198 j WNW 0 24 89 95 13 1 222 il 1 NW 4 37 122 103 40 9 315 NNW 2 42 134 86 14 0 278 TOT 88 540 1481 1097 196 28 3430 Hours of Calm Data: 0 Hours of Invalid Data: 103 i

Page 13 of 15 I

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TABLE 4 (continued)

Union Electric - Callaway Plant Report Date/ Time: 26-APR-199610:47:58.47 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1995 00:00:00.00 to 31 DEC-1995 23:00:00.00 Stability Class: F Wind speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 4 18 16 5 5 53 NNE 2 14 30 12 4 2 64 NE 3 17 45 1 1 2 69 ENE O 9 41 6 0 0 56 E O 18 60 14 0 0 92 ESE O 18 77 8 0 0 103 SE I 17 91 35 0 0 144 SSE 0 19 103 66 1 0 189 S 2 26 112 61 0 0 201 SSW l 10 54 64 0 0 129 SVV 3 12 35 37 9 0 96 WSW 3 11 22 5 3 0 44 NV 1 8 24 28 0 0 61 WNW 3 9 32 21 2 0 67 NW 4 12 30 16 6 0 68 NNW 4 9 40 33 2 0 88 TOT 32 213 814 423 33 9 1524 Hours of Calm Data: 0 Hours of Invalid Data: 52 Page 14 of 15

TABLE 4 (continued) I1l i

' Union Electric - Callaway Plant Report Date/fime: 26-APR-199610:47:58.47 1

Meteorological Data gl Totals of Hours at Each Wind Speed & Direction g 1-JAN-1995 00:00:00.00 to 31-DEC-1995 23:00:00.00 Stability Class: G I

Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I N 0 4 7 9 1 2 23 NNE G 6 10 7 0 0 23 NE O 9 31 7 0 0 47 i l

ENE O 6 23 11 0 0 40 E O 3 36 3 0 0 42 ESE O 4 16 1 0 0 21 SE O 6 13 5 0 0 24 SSE I 11 12 19 0 0 43 S 0 51 I,

11 14 0 0 76  ;

SSW l 10 27 18 5 0 61 SW 0 9 24 14 1 0 48 WSW 0 6 7 5 0 0 18 W 0 3 8 7 6 0 24 l

WNW 0 5 14 3 0 0 22 l NW l 2 7 5 5 2 22 NNW 0 7 10 15 0 10 42 TOT 3 102 296 143 18 14 576 Hours of Calm Data: 0 Hours ofInvalid Data: 60 '

Hours of Good Data: 8400 = 95.99f of Total flours Page 15 of 15

TABLE 5 DOSE AT THE SITE BOUNDARY AND TO THE NEAREST RESIDENT FROM GASEOUS EFFLUENTS SITE BOUNDARY NEAREST RESIDENT LOCATION: 1.40 km SSE LOCATION: 1900.00 km WSW AGE GROUP: CHILD AGE GROUP: CHILD ORGAN UNITS DOSE  % LIMIT (a) DOSE  % LIMIT (b)

1. GAMMA AIR DOSE
  • MRAD 1.06E-03 0.01 7.65E-04 N/A
2. BETA AIR DOSE
  • MRAD 1.78E-03 0.01 1.28E-03 N/A
3. WHOLE BODY *** MREM 2.51E-03 N/A 1.31E-03 N/A
4. SKIN "* MREM 3.56E-03 N/A 2.07E-03 N/A
5. BONE ** MREM 1.55E-03 N/A. 2.58E-03 0.02
6. LIVER " MREM 4.18E-03 N/A 1.96E-02 0.13
7. TOTAL BODY ** MREM 4.18E-03 N/A 1.79E-02 0.12 l
8. THYROID ** MREM 4.22E-03 N/A 2.04E-02 0.14
9. KIDNEY ** MREM 4.18E-03 N/A 1.82E-02 0.12
10. LUNG " MREM 4.26E-03 N/A 1.78E-02 0.12 I I . GI-LLI *
  • MREM 4.18E-03 N/A 1.77E-02 0.12
  • Dose from Noble Gases only

" Dose from Tritium, Radioiodines, and Particulates only

      • Dose from Noble Gases plus Ground Plane dose (a) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 10 mrad gamma air dose and 20 mrad beta air dose.

(b) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 15 mrem to any organ from I-131.1 133, H-3 and particulate radionuclides with haltlives greater than 8 days, n

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TABLE 6 DOSE TO THE MEMBER OF THE PUBLIC FROM ACTIVITIES WITHIN THE SITE BOUNDARY "

EFFLUENT DIRECT DIRECT TOTAL I

DOSE WITHIN RADIATION RADIATION DOSE THE SITE E ORGAN UNITS BOUNDARY FROM THE UNIT FROM OUTSIDE FOR THE g TANKS YEAR

1. SKIN MREM 5.00E-(M N/A N/A 5.00E-04 I ~
2. BONE MREM 5.94E-02 8.79E-03 2.85E-04 6.84E-02
3. LIVER MREM 6.02E-02 8.79E-03 2.85E-04 6.93E-02
4. 'iOTAL BODY MREM 6.04E-02 8.79E-03 2.85E-04 6.95E-02
5. THYROID MREM 6.02E-02 8.79E-03 2.85E-04 6.93E-02
6. KIDNEY MREM 6.02E-02 8.79E-03 2.85E-04 6.93E-02
7. LUNG MREM 6.02E-02 8.79E-03 2.85E-04 6.93E-02
8. GI-LLI MREM 6.02E-02 8.79E-03 2.85E-04 6.93 E-02 l

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, TABLE 7 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE (MEMBER OFTHE PUBLIC)

DOSE FROM TOTAL DOSE DOSE ATTHE ACTIVITIES TO THE RESIDENCE WITHIN SITE MEMBER OF i ORGAN UNITS ' LOCATION BOUNDARY THE PUBLIC % LIMITS *

1. SKIN MREM - 6.36E-04 5.00E-04 1.14E-03 0.00
2. BONE MREM 7.88E-04 6.84E-02 6.92E-02 0.28
3. LIVER MREM 5.22E-03 6.93E-02 7.45E-02 0.30
4. TOTAL BODY MREM 5.38E-03 6.95E-02 7.49E-02 0.30
5. THYROID MREM 5.39E-03 '6.93E-02 7.47E-02 0.10
6. KIDNEY MREM 4.86E-03 6.93E-02 7.41E-02 0.30
7. LUNG MREM 4.75E-03 6.93E-02 7.41E-02 i

0.30

8. GI-LLI MREM 4.95E-03 6.93E-02 7.42E-02 0.30
  • Annual dose limits from'40CFR190.10(a) of 25 mrem whole body,75 mrem to the thyroid, and 25 mrem to any other organ.

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TABLE 8 DOSE DUE TO LIQUID EFFLUENTS (MEMBER OF THE PUBLIC) 1995 ORGAN UNITS DOSE ** LIMIT *  % LIMIT

1. BONE MREM 7.96E-03 10.00 7.96E-02 I
2. LIVER MREM 2.00E-02 10.00 2.00E-01
3. TOTAL BODY MREM 1.74E-02 3.00 5.80E-01
4. THYROID MREM 1.09E-02 10.00 1.09E-01
5. KIDNEY MREM 1.40E-02 10.00 1.40E-01
6. LUNG MREM 1.19E-02 10.00 1.19E-01
7. GI-LLI MREM 1.98E-02 10.00 1.98E-01
  • Annual dose limits of APA-ZZ-01003, Section 9.4.1.1.
    • Reported dose includes the dose from the Logan Creek event I

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ATTACHMENT 1 f APA-ZZ-01003, OFFSITE DOSE CALCULATION MANUAL, REVISION 5

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